Analysis of burnup performance and temperature coefficient for a small modular molten-salt reactor started with plutonium
Xue-Chao Zhao, Yang Zou, Rui Yan, X. Z. Cai
Topics & Concepts
BurnupPlutoniumMolten salt reactorMolten saltThorium fuel cycleNuclear engineeringActinideSpent nuclear fuelLiquid fluoride thorium reactorMOX fuelUraniumMaterials scienceVolume (thermodynamics)RadiochemistryChemistryNuclear reactorNuclear chemistryMetallurgyThermodynamicsPhysicsEngineeringNuclear reactor physics and engineeringNuclear Materials and PropertiesFusion materials and technologies